2016
DOI: 10.1088/0031-8949/t167/1/014077
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Nitrogen retention mechanisms in tokamaks with beryllium and tungsten plasma-facing surfaces

Abstract: Global gas balance experiments at ASDEX Upgrade (AUG) and JET have shown that a considerable fraction of nitrogen injected for radiative cooling is not recovered as N 2 upon regeneration of the liquid helium cryo pump. The most probable loss channels are ion implantation into plasma-facing materials, co-deposition and ammonia formation. These three mechanisms are investigated in laboratory and tokamak experiments and by numerical simulations. Laboratory experiments have shown that implantation of nitrogen ions… Show more

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Cited by 21 publications
(19 citation statements)
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“…As has been previously reported [4,7,10,11], the mass spectra of ammonia are expected to overlap with those of methane and water, which are also present in the neutral phase during the discharge phases, with varying ratios of hydrogen and deuterium atoms. In order to distinguish between the contributions of the three impurities to the mass spectrometer recordings, a statistical model, described in detail in [7,11] has been fit to the data.…”
Section: Ammoniamentioning
confidence: 56%
See 3 more Smart Citations
“…As has been previously reported [4,7,10,11], the mass spectra of ammonia are expected to overlap with those of methane and water, which are also present in the neutral phase during the discharge phases, with varying ratios of hydrogen and deuterium atoms. In order to distinguish between the contributions of the three impurities to the mass spectrometer recordings, a statistical model, described in detail in [7,11] has been fit to the data.…”
Section: Ammoniamentioning
confidence: 56%
“…In all three locations, for the non-seeded discharges, the fit reported non-zero pressures of ammonia. As no ammonia formation was expected in a nonseeded discharge [4,7,13,14], the reported ammonia pressures from the non-seeded discharge can serve as an estimate of the reliability of the detection.…”
Section: Ammoniamentioning
confidence: 96%
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“…Due to the need to ensure tritium self-sufficiency, the vessel in the future fusion devices will be surrounded by the breeding blanket, which will severely limit the access to the plasma. Residual gas analysis (RGA) has already been shown to provide information about certain plasma-wall interaction processes in fusion devices (5,6). As it does not require direct access to the plasma, nor immediate vicinity to the plasma containing vessel, it is a suitable candidate for use in future, diagnostic-limited fusion devices.…”
Section: Introductionmentioning
confidence: 99%